ML17254A185
| ML17254A185 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 01/29/1985 |
| From: | Maier J ROCHESTER GAS & ELECTRIC CORP. |
| To: | Zwolinski J Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17254A186 | List: |
| References | |
| NUDOCS 8502040201 | |
| Download: ML17254A185 (3) | |
Text
REGULATOR INFORMATION DISTRIBUTION, TEM (RIDS)
ACCESSION NBR:8502040201, DOC,DATE: 85/01/29 NOTARIZED:.NO FACIL:50 244 Robert Emmet Ginna Nuclear Plants Unit ii Rochester G
AUTH'AME AUTHOR AFFILIATION MAIERtJ ~ E ~
Rochester Gas 8
El ectric Corp ~
REC IP ~ NAME RECIPIENTAFFILIATION ZWOLINSKI,J.A, Operating Reactors Branch 5
SUBJECT:
Forwards Rev 3 to Procedure PC",25.4i "Guidelines for.
Interpreting Post"Accident Sampling Resu)ts to,Estimate Reactor Core Damage~"
based on Hestinghouse Owners Gr oug core damage assessment methodology'ISTRIBUTION CDDE:
AOOID CDPIES RECEIVEDiLTR J" ENCL J SIZE: Jg TITLE:
OR Submittal:
General Distribution NOTES:NRR/DL/SEP 1cy ~
OL:09/19/69 DOCKET.
05000244 05000244 RECIPIENT ID CODE/NAME NRR ORBS BC 01 INTERNAL: ACRS 09 ELD/HDS4 NRR/DL DIR NRR/DL/TSRG NRR/DSI/RAB RGNi COPIES LTTR ENCL 7
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1 1
1 1
1 RECIPIENT ID CODE/NAME ADM/LFMB, NRR/DE/MTEB NRR/DL/ORAB I/METB G FILE 04 COPIES LTTR ENCL 0
1 1
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1 1
1 1
EXTERNAL: LPDR NSIC NOTES:
03 05 1
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1 NRC PDR 02 TOTAL NUMBER OF COPIES REQUIRED:
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i" JEre IIIIZZ(Z ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649 0001 JOHN E. MAIER SENIOR VICE PRESIDENT OPERATIONS ANO ENGINEERING TELEPHONE aREa cooE TIE 54&2700 January 29 I 1985 Director of Nuclear Reactor Regulation Attention:
Mr. John A. Zwolinskii Chief Operating Reactors Branch No.
5 U.S. Nuclear Regulatory Commission Washington>
D.C.
20555
Subject:
Core Damage Assessment by Radiological Analysis R. E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Zwolinski:
Enclosed is the procedure for estimating reactor core damage by radiological and chemical analysis.
The procedure is based on the Westinghouse Owners Group Core Damage Assessment Methodology and is specific for the R. E. Ginna Nuclear Power Plant.
Very truly yours>
Enclosure 8502040201 850i 29 PDR ADDCK 05000244 PDR ~
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